17–22 May 2026
marinaforum REGENSBURG
Europe/Berlin timezone

1.044 Beam fueling low recycling discharges with modest lithium impurity fraction in LTX-beta

18 May 2026, 16:10
2h 30m
Poster C. Plasma Fueling, Particle Exhaust and Control, Tritium Retention Postersession 1

Speaker

Anurag Maan (Princeton Plasma Physics Laboratory)

Description

We show that beam fueling of a low recycling discharge with low energy neutral beams is feasible with modest (~ 5%) lithium impurity concentrations. Low recycling discharges (R ~ 0.5) on LTX-beta have been documented with a near flat electron temperature profile. Edge temperature measurements in the SOL indicate a hot and sparse SOL with collisionality < 0.1 and values as low as 0.01. Low gradients in electron and ion temperature profiles are predicted to suppress temperature gradient driven instabilities and enhance confinement. High confinement discharges on LTX-beta can reach a H-98 of close to 2 in a limited plasma without H-mode, in the complete absence of a pressure pedestal. Fueling a low recycling discharge while maintaining a hot edge is non-trivial and will likely only be tractable either with neutral beams or with pellet injection from the high field side. Gas puffing will lead to a collapse of the hot edge. LTX-beta was recently vented to increase the tangency radius of the neutral beam. Fast ion orbit modeling indicated that injecting the beam at larger tangency radius reduces the first orbit losses and improves beam coupling. LTX-beta now shows beam fueling. Charge exchange cross section of beam hydrogen neutrals on Li ions can be 10-15 times the charge exchange cross section of beam hydrogen neutrals on ionized hydrogen from the plasma. Therefore, the effect has a functional dependence on the core lithium impurity fraction, this effect will be explored. Beyond fueling hot edge, high confinement discharges with low recycling, these results indicate a path to fueling tokamaks and stellarators by introducing a modest lithium impurity fraction; similar results are predicted for a fusion plasma with a modest helium ash fraction. A modest lithium impurity has little effect on Z effective, and would getter common higher Z impurities present on the surfaces of metallic plasma facing such as carbon and oxygen. Results for neutral beam fueling with solid and liquid lithium plasma-facing surfaces will be presented. The dependence of beam fueling on lithium concentration and on surface conditions as monitored by in-situ secondary ion mass spectroscopy and temperature programmed desorption will be discussed.

This work is supported by USDoE contracts DE-AC02-09CH11466, DE-AC52-07NA27344.

Authors

Anurag Maan (Princeton Plasma Physics Laboratory) Dr Dennis Boyle (Princeton Plasma Physics Laboratory, Princeton) Dick Majeski (PPPL) Dr Santanu Banerjee (Princeton Plasma Physics Laboratory, Princeton) George Wilkie (Princeton Plasma Physics Laboratory) Dr Mate Lampert (Princeton Plasma Physics Laboratory) Ms Camila López Pérez (Nuclear Engineering, Penn State University, State College, PA, USA) Dr Ricardo Shousha (Princeton Plasma Physics Laboratory, Princeton) Mr Tosh Le (Princeton Plasma Physics Laboratory, Princeton) Dr William Capecchi (Physics, University of Wisconsin, Madison,WI 53706) Dr Leonid Zakharov (LiWFusion, PO Box 2391, Princeton, NJ 08543, USA) Mr Pranshu Agarwal (LiWFusion, PO Box 2391, Princeton, NJ 08543, USA) Mr Hussein Gajani (Physics, University of Wisconsin, Madison,WI 53706) Mr Shigeyuki Kubota (Princeton Plasma Physics Laboratory, Princeton, NJ 08543 USA) Tanmay Macwan (Lawrence Livermore National Laboratory, USA) Vsevolod Soukhanovskii (LLNL)

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